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Chemicals identified in human biological media: a data base. Third annual report, October 1981 (open access)

Chemicals identified in human biological media: a data base. Third annual report, October 1981

Data from almost 1600 of the 3800 body-burden documents collected to date have been entered in the data base as of October 1981. The emphasis on including recent literature and significant research documents has resulted in a chronological mix of articles from 1974 to the present. When body-burden articles are identified, data are extracted and entered in the data base by chemical and tissue/body fluid. Each data entry comprises a single record (or line entry) and is assigned a record number. If a particular document deals with more than one chemical and/or tissue, there will be multiple records for that document. For example, a study of 5 chemicals in each of 3 tissues has 15 different records (or 15 line entries) in the data base with 15 record numbers. Record numbers are assigned consecutively throughout the entire data base and appear in the upper left corner of the first column for each record.
Date: December 1, 1981
Creator: Cone, M.V.; Baldauf, M.F. & Martin, F.M. (comps.)
System: The UNT Digital Library
Chemicals identified in human biological media: a data base. Third annual report, October 1981 (open access)

Chemicals identified in human biological media: a data base. Third annual report, October 1981

Part 2 contains the data base in tabular format. There are two sections, the first with records on nondrug substances, and the second with records on drugs. Chemicals in each section are arranged alphabetically by CAS preferred name, CAS registry number, formula, atomic weight, melting point, boiling point, and vapor pressure. Tissues are listed alphabetically with exposure route, analytical method, number of cases, range, and mean - when available in the source document. A variety of information may also be included that is pertinent to the range and mean as well as experimental design, demography, health effects, pathology, morphology, and toxicity. Review articles are included in the data base; however, no data have been extracted from such documents because the original research articles are included.
Date: December 1, 1981
Creator: Cone, M.V.; Baldauf, M.F. & Martin, F.M. (comps.)
System: The UNT Digital Library
Chemistry and morphology of coal liquefaction. Quarterly report, October 1-December 31, 1981 (open access)

Chemistry and morphology of coal liquefaction. Quarterly report, October 1-December 31, 1981

Progress reports are presented for the following six tasks: (1) selective synthesis of gasoline range components from synthesis gas; (2) electron microscopy studies of coal during hydrogenation; (3) catalysed low temperature hydrogenation of coal; (4) selctive hydrogenation, hydrogenolysis and alkylation of coal and coal liquids by organo-metallic systems; (5) chemistry of coal solubilization and liquefaction; (6) coal conversion catalysts-deactivation studies. Highlights are as follows: (1) In the presence of hydrogen and the absence of base, using the catalyst RuCl/sub 2/ (CO)/sub 2/ (phi/sub 3/ P)/sub 2/ excellent yields of reduced polynuclear heteroaromatic nitrogen compound were produced with 100% selectivity for the N-containing ring. (2) A careful gas chromatographic analysis of Fischer-Tropsch products has shown that major peaks, previously thought to be single compounds are composites of two or more compounds. Resolution of these peaks will enable one to establish a rational grouping of n/i and paraffin/olefin ratios. (3) Addition of iron or rhodium to potassium impregnated graphite did not result in the production of heavier hydrocarbons than methane from the graphite-steam reaction at low temperature. However, small amounts of iron enhanced the methane production. (ATT)
Date: December 1, 1981
Creator: Heinemann, H.
System: The UNT Digital Library
Coated particle waste form development (open access)

Coated particle waste form development

Coated particle waste forms have been developed as part of the multibarrier concept at Pacific Northwest Laboratory under the Alternative Waste Forms Program for the Department of Energy. Primary efforts were to coat simulated nuclear waste glass marbles and ceramic pellets with low-temperature pyrolytic carbon (LT-PyC) coatings via the process of chemical vapor deposition (CVD). Fluidized bed (FB) coaters, screw agitated coaters (SAC), and rotating tube coaters were used. Coating temperatures were reduced by using catalysts and plasma activation. In general, the LT-PyC coatings did not provide the expected high leach resistance as previously measured for carbon alone. The coatings were friable and often spalled off the substrate. A totally different concept, thermal spray coating, was investigated at PNL as an alternative to CVD coating. Flame spray, wire gun, and plasma gun systems were evaluated using glass, ceramic, and metallic coating materials. Metal plasma spray coatings (Al, Sn, Zn, Pb) provided a two to three orders-of-magnitude increase in chemical durability. Because the aluminum coatings were porous, the superior leach resistance must be due to either a chemical interaction or to a pH buffer effect. Because they are complex, coated waste form processes rank low in process feasibility. Of all the …
Date: December 1, 1981
Creator: Oma, K. H.; Buckwalter, C. Q. & Chick, L. A.
System: The UNT Digital Library
Comparison of computed reaction rates using different methods and data for the STARFIRE and TMHR benchmark blankets (open access)

Comparison of computed reaction rates using different methods and data for the STARFIRE and TMHR benchmark blankets

RAFFLE Monte Carlo calculations using ENDF/B V5 data have been performed for the TMHR suppressed fission benchmark blanket and the STARFIRE Reference Design blanket. One-dimensional cylindrical geometry was employed. ANISN S/sub N/ calculations were also done for both blankets using the DLC37F, FLUNG, and MACKLIB IV data sets. Reaction rates from RAFFLE and ANISN are compared with each other and with results obtained by the blanket designers (ANL, TRW, GA). The purposes of this study are to: (1) partially validate the new RAFFLE libraries for fusion neutronics and, (2) lend confidence to the results of previous ANISN calculations that were done to investigate the feasibility of fusion blanket testing in the Engineering Test Reactor. For both blankets, the tritium breeding ratio (TBR) predicted by RAFFLE and ANISN agree within 3%. For TMHR, our TBR results lie in between those obtained by TRW and GA, which disagree by 10 to 15%. For STARFIRE, our TBR results are 7 to 10% lower than ANL's values. The reason for the large discrepancies is unknown. However, it is concluded that modeling errors are unlikely so that data sources and processing differences used to generate cross section libraries are implied. Additional investigation is needed to …
Date: December 1, 1981
Creator: Scott, A.J. & Takata, M.L.
System: The UNT Digital Library
Comparison of techniques for preserving dissolved nutrients in open-ocean seawater samples (open access)

Comparison of techniques for preserving dissolved nutrients in open-ocean seawater samples

A survey of recent literature on methods for preserving nutrients indicates that the major factors which have been considered are: filtration and type of filter, material and history of storage containers, the influence of light, storage temperature and how it is achieved, the effectiveness of various acids, poisons, and preservatives, and the source of the sample. No comprehensive studies of open ocean seawater were found. A comprehensive study of nutrient preservation techniques was conducted on surface and deep seawater samples collected in the Gulf Stream east of Miami, Florida. No preservation techniques were found to be satisfactory for near-surface open ocean seawater. Results for deep water samples are found to be substantially better. The degree of preservation was not substantially improved by complex techniques involving freezing and chemical additives. Storage of filtered samples in aged polyethylene bottles at 2/sup 0/C in the dark is recommended for samples that must be stored. (LEW)
Date: December 1, 1981
Creator: Morse, J. W.; Hunt, M.; Zullig, J.; Mucci, A. & Mendez, T.
System: The UNT Digital Library
Compatibility of the Zr-Al alloy with a tokamak plasma environment (open access)

Compatibility of the Zr-Al alloy with a tokamak plasma environment

We have investigated the compatibility of the Zr-Al alloy bulk getter with a tokamak plasma environment, where the hydrogenic fluxes are sufficient to cause embrittlement in relatively short times. Under normal operating conditions with the getters activated, it is necessary to regenerate the absorbed hydrogenic species before the embrittlement limit is reached. We present a method for determining the loading under tokamak conditions where the Zr-Al surface characteristics can change. During glow discharge cleaning and pulse discharge cleaning, it is not convenient to regenerate. We find, however, that during the cleaning operations the getter self-inerts, thus limiting the loading. We present data and a model which accounts for this behavior in terms of impurity adsorption on the room temperature getter surface during the cleaning operations.
Date: December 1, 1981
Creator: Knize, R. J.; Cecchi, J. L. & Dylla, H. F.
System: The UNT Digital Library
Comprehensive energy-management program. Hybrid photovoltaic/thermal absorber. Annual report, September 1, 1980-December 31, 1981 (open access)

Comprehensive energy-management program. Hybrid photovoltaic/thermal absorber. Annual report, September 1, 1980-December 31, 1981

Research work was done during the reporting period on the two-part research program: (A) to improve energy conservation through increased unit and system efficiencies, energy management, and system optimization, and (B) to develop a novel, low-cost hybrid photovoltaic/thermal absorber. Performance tests were conducted on all the boilers and chillers on campus. Several corrective measures were indicated and implemented. A detailed survey of energy use by functions and consumption/demand study has been in progress. A preliminary computer simulation model of the entire campus has been developed and made operational. It has been demonstrated both analytically and experimentally that the reradiation losses from the absorber can be reduced significantly by utilizing a light-pipe absorber. Two paraboloidal dishes, one of 6 ft diameter and the other of 20 ft diameter have been utilized. Collector efficiencies have been measured at coolant outlet temperatures up to 282/sup 0/C with a square light-pipe absorber and with 6 ft diameter concentrator. Laser ray testing was conducted on both the 6 ft and 20 ft diameter concentrators. Design of the total energy absorber has been completed.
Date: December 1, 1981
Creator: Kumar, G. N.; Sellers, J. P. & Dybczak, Z. W.
System: The UNT Digital Library
Computing a Trust Region Step (open access)

Computing a Trust Region Step

An algorithm is proposed for the problem of minimizing a quadratic function subject to an ellipsoidal constraint which is guaranteed to produce a nearly optimal solution in a finite number of iterations. A robust and efficient algorithm for this problem is required to compute the step between iterates in trust region methods for optimization problems. We also consider the use of our algorithm in a trust region Newton's method. In particular, we prove that under reasonable assumptions the sequence (X/sub k/) generated by Newton's method has a limit point X* which satisfies the first and second order necessary conditions for a minimizer of the objective function f. Numerical results for GQTPAR, which is a Fortran implementation of our algorithm, show that GQTPAR is quite successful in a trust region method. In our tests a call to GQTPAR only required 1.6 iterations on the average.
Date: December 1981
Creator: Moré, Jorge J. & Sorensen, D. C.
System: The UNT Digital Library
Concepts of fundamental processes related to gasification of coal. Quarterly progress report, July-September 1981 (open access)

Concepts of fundamental processes related to gasification of coal. Quarterly progress report, July-September 1981

The research projects are described: (1) single stage catalytic coal gasification is an attractive concept as a direct method of producing high BTU gas from coal. This process involves the introduction of a coal-solvent slurry and hydrogen gas into a fixed bed catalytic reactor, which employs a catalyst high in hydrogenation and cracking activity. Steam may also be added to the system. The gas produced will be principally methane. Thermodynamic calculations indicate that this process is essentially autothermal. Since this process utilizes the heat of methanation to a maximum extent, significant overall energy savings can be achieved over the more conventional multi-stage gasification systems. The primary objective of this research is to optimize the process variables to maximize methane yields. Initially, a sulfided Ni-W/SiO/sub 2/-Al/sub 2/O/sub 3/ catalyst will be used; (2) the demand for molecular hydrogen and for synthesis gas is rapidly increasing. Therefore, an extensive program on steam reforming of aromatic compounds such as benzene, substituted benzenes, naphthalene and other aromatics found in coal and coal-derived liquids (CDL) is being carried out. The combination of coal liquefaction-steam reforming of CDL could prove to be an important alternative to coal gasification for the production of SNG and hydrogen. An …
Date: December 1, 1981
Creator: Wiser, W.H.
System: The UNT Digital Library
Consolidated fuel reprocessing program. Progress report, July 1-September 30, 1981 (open access)

Consolidated fuel reprocessing program. Progress report, July 1-September 30, 1981

Technical progress is reported in overview fashion in the following areas: process development, laboratory R and D, engineering research, engineering systems, integrated equipment test facility (IET) operations, and HTGR fuel reprocessing. (DLC)
Date: December 1, 1981
Creator: unknown
System: The UNT Digital Library
Continuum modeling of two-phase flows (open access)

Continuum modeling of two-phase flows

Continuum modeling of two-phase flows can essentially be achieved in two ways. The first approach, the so-called continuum theory of mixtures, ignores the details of the flow occurring on the microscopic level, while the second one is the result of some averaging procedure. Although they both lead, as expected, to the same set of basic equations, they differ strongly in their spirit when closure equations have to be found. In the present report, we have attempted to give a brief critical review of both approaches, to compare them and to discuss some of the major difficulties which arise. It is shown that the application of the continuum theory of mixtures is, in most cases, questionable and that the only appropriate way of finding closure equations, besides correlating experimental results, consists in a useful investigation of the microscopic flow pattern associated with an adequate averaging technique.
Date: December 1, 1981
Creator: Bataille, J. & Kestin, J.
System: The UNT Digital Library
Copper laser diagnostics and kinetics support (open access)

Copper laser diagnostics and kinetics support

In the effort MSNW participated with the LINL copper-Vapor Laser Program by providing a useful plasma diagnostic for interpretation of Copper-vapor laser kinetics. MSNW developed and delivered a pulsed interferometric diagnostic package to LLNL. Moreover MSNW provided personal services at the request and direction of LLL in the implementation of the diagnostic and interpretation of the data.
Date: December 1, 1981
Creator: unknown
System: The UNT Digital Library
Correlation of Acoustic Emission Generated During Uniform Biaxial Loading to Microstructural Sources in 7075-T651 Aluminum and 21Cr-6Ni-9Mn Stainless Steel. Final Report (open access)

Correlation of Acoustic Emission Generated During Uniform Biaxial Loading to Microstructural Sources in 7075-T651 Aluminum and 21Cr-6Ni-9Mn Stainless Steel. Final Report

This paper reports on the effect on acoustic emission (AE) of uniform biaxial loading of a thin-walled tube designed by Hamstad, Patterson and Mukherjee. The AE generated during biaxial loading of 7075-T651 aluminum and 21Cr-6Ni-9Mn stainless steel had several anomalous features relative to tensile generated AE. The biaxial AE data was of a much higher level and peaked at a lower strain than the uniaxial AE response. A particle cracking model was proposed in which inclusions with the largest projected surface area perpendicular to the principal axis of applied loading will crack before smaller inclusions, and the resulting energy released per AE will be proportional to the crack surface area. The inclusion contents were studied with respect to size, shape, density, hardness, and fracture/decohesion behavior. The inclusions in both 7075-T651 and 21-6-9 display the preferred cracking orientation predicted in the Hamstad, et al. model and are shown to be associated with the generated AE. However, other factors appear to contribute to the total AE responses. There is evidence that for 7075-T651 subjected to biaxial loading, a grain boundary-related mechanism becomes a significant source of AE in the latter stages of strain hardening. Also, for both materials, the complex applied load …
Date: December 1, 1981
Creator: Leon, E. & Mukherjee, A. K.
System: The UNT Digital Library
Cost Effectiveness of Influenza Vaccination (open access)

Cost Effectiveness of Influenza Vaccination

A study by the Office of Technology Assessment (OTA) that "evaluates influenza vaccination on the basis of another criterion-cost effectiveness"
Date: December 1981
Creator: United States. Congress. Office of Technology Assessment.
System: The UNT Digital Library
Creep properties of forged 2219 T6 aluminum alloy shell of general-purpose heat source-radioisotope thermoelectric generator (open access)

Creep properties of forged 2219 T6 aluminum alloy shell of general-purpose heat source-radioisotope thermoelectric generator

The shell (2219 T6 aluminum forging) of the General Purpose Heat Source-Radioisotope Thermoelectric Generator was designed to retain the generator under sufficient elastic stress to secure it during space flight. A major concern was the extent to which the elastic stress would relax by creep. To determine acceptability of the shell construction material, the following proof tests simulating service were performed: 600 h of testing at 270/sup 0/C under 24.1 MPa stress followed by 10,000 h of storage at 177/sup 0/C under 55.1 MPa, both on the ground; and 10,000 h of flight in space at 270/sup 0/C under 34.4 MPa stress. Additionally, systematic creep testing was performed at 177 and 260/sup 0/C to establish creep design curves. The creep tests performed at 177/sup 0/C revealed comparatively large amounts of primary creep followed by small amounts of secondary creep. The early creep is believed to be abetted by unstable substructures that are annealed out during testing at this temperature. The creep tests performed at 270/sup 0/C showed normal primary creep followed by large amounts of secondary creep. Duplicate proof tests simulating the ground exposure conditions gave results that were in good agreement. The proof test simulating space flight at 270/sup …
Date: December 1, 1981
Creator: Hammond, J.P.
System: The UNT Digital Library
Criteria for the evaluation of a dilute decontamination demonstration (open access)

Criteria for the evaluation of a dilute decontamination demonstration

This document provides the prerequisite technical information required to evaluate and/or develop a project to demonstrate the dilute chemical decontamination of the primary coolant system of light water reactors. The document focuses on five key areas: the basis for establishing programmatic prerequisites and the key decision points that are required for proposal evaluation and/or RFP (Request for Proposal) issuance; a technical review of the state-of-the-art to identify the potential impacts of a reactor's primary-system decontamination on typical BWR and PWR plants; a discussion of the licensing, recertification, fuel warranty, and institutional considerations and processes; a preliminary identification and development of the selection criteria for the reactor and the decontamination process; and a preliminary identification of further research and development that might be required.
Date: December 1, 1981
Creator: FitzPatrick, V.F.; Divine, J.R.; Hoenes, G.R.; Munson, L.F. & Card, C.J.
System: The UNT Digital Library
Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched U02 Rods in Water with Uranium or Lead Reflecting Walls Undermoderated Water-to-Fuel Volume Ratio of 1.6 (open access)

Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched U02 Rods in Water with Uranium or Lead Reflecting Walls Undermoderated Water-to-Fuel Volume Ratio of 1.6

A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% and 4.31 wt% {sup 235}U enriched UO{sub 2} rods in water were performed to provide data on the reactivity effects of lead and depleted uranium reflecting walls. This data furnishes well defined benchmarks for use in validating calculational techniques employed in analyzing fuel shipping and storage systems having lead or uranium biological shields. For each fuel enrichment, the critical separation between three subcritical fuel clusters was observed to increase as either 77mm thick depleted uranium or 102mm thick lead reflecting walls were moved towards the fuel. A maximum critical separation was observed for both the lead and the depleted uranium reflecting walls with a water gap between the fuel clusters and the reflecting walls. For both fuel enrichments, this optimum water gap was about 25mm for the depleted uranium walls and about lOmm for the lead walls.
Date: December 1, 1981
Creator: Bierman, S. R.; Durst, B. M. & Clayton, E. D.
System: The UNT Digital Library
Curvature-driven instabilities in a hot-electron plasma: radial analysis (open access)

Curvature-driven instabilities in a hot-electron plasma: radial analysis

The theory of unfavorable curvature-driven instabilities is developed for a plasma interacting with a hot electron ring whose drift frequencies are larger than the growth rates predicted from conventional magnetohydrodynamic theory. A z-pinch model is used to emphasize the radial structure of the problem. Stability criteria are obtained for the five possible modes of instability: the conventional hot electron interchange, a high-frequency hot electron interchange (at frequencies larger than the ion cyclotron frequency), a compressional instability, a background pressure-driven interchange, and an interacting pressure-driven interchange.
Date: December 1, 1981
Creator: Berk, H. L.; Van Dam, J. W.; Rosenbluth, M. N. & Spong, D. A.
System: The UNT Digital Library
Cycling of transuranic radionuclides in the Columbia River, its Estuary, and the Northeast Pacific Ocean. Progress report, February 1981-December 1981 (open access)

Cycling of transuranic radionuclides in the Columbia River, its Estuary, and the Northeast Pacific Ocean. Progress report, February 1981-December 1981

Progress from February, 1981 through December, 1981 in research dealing with the behavior of transuranic and other radionuclides in the Columbia River downstream from the Hanford Reservation is summarized. All of the objectives outlined in last year's renewal proposal except one were met. The analyses of all cores raised from the Columbia River between McNary Reservoir and the mouth of the river were completed. This permits the establishment of a budget for Pu and Am. Analyses of four natural matrix standard reference materials for the National Bureau of Standards were also performed.
Date: December 1, 1981
Creator: Beasley, T.M.
System: The UNT Digital Library
Data report for the Northeast Residential Experiment Station, November 1981 (open access)

Data report for the Northeast Residential Experiment Station, November 1981

Physical performance data for the month of November 1981 obtained from photovoltaic energy systems under test at the Northeast Residential Experiment Station in Concord, Massachusetts are tabulated.
Date: December 1, 1981
Creator: Russell, M. C.; Raghuraman, P. & Mahoney, P. C.
System: The UNT Digital Library
Design and development of a split-evaporator heat-pump system (open access)

Design and development of a split-evaporator heat-pump system

The designs and experimental results of three types of multiple source heat pumps are presented. The three designs are the parallel evaporator, the series evaporator, and the parallel evaporator with active subcooling, with the parallel evaporator with the active subcooling showing the most promise for solving the problem of defrosting of air evaporators. Three design procedures for multiple source heat pumps were developed. One of these is a hand calculational procedure, the others are computer based. The models are based upon the refrigerant flow rate, rather than the refrigeration effect of the evaporator. The technical results of a detailed analytical and experimental model of the heat transfer rates on a flat plate ice maker are presented. It is shown, both analytically and experimentally, that the temperature of the air surrounding the flat plate ice maker can play a dominant role in the rate of ice formation. A detailed weather analysis for forty cities located throughout the nation was completed. These data were processed to allow easy computation of thermal storage requirements for full, partial, or minimum ACES systems, or upon other design requirements, such as off-peak air conditioning. The results of an innovative ice storage system that is thermally coupled …
Date: December 1, 1981
Creator: Somerville, M.H. & Penoncello, S.G.
System: The UNT Digital Library
Design and fabrication of polymer-concrete-lined pipe for testing in geothermal-energy processes. Final report (open access)

Design and fabrication of polymer-concrete-lined pipe for testing in geothermal-energy processes. Final report

A specific polymer-concrete formulation was applied as a steel pipe liner in response to a need for durable, economical materials for use in contact with high temperature geothermal brine. Processes are described for centrifugally applying the liner to straight pipe, for casting the liner in pipe fittings, and for closure of field joints. Physical properties of the liner materials were measured. Compressive strengths of up to 165.8 MPa (24,045 psi) and splitting tensile strengths of 23.5 MPa (3408 psi) were measured at ambient temperature. Compressive strengths of 24 MPa (3490 psi) and splitting tensile strengths of 2.5 MPa (366 psi) were measured at about 150/sup 0/C (302/sup 0/F). A full-scale production plant is described which would be capable of producing about 950 m (3120 ft) of lined 305-mm-diam (12 in.) pipe per day. Capital cost of the plant is estimated to be about $8.6 million with a calculated return on investment of 15.4%. Cost of piping a geothermal plant with PC and PC-lined steel pipe is calculated to be $1.21 million, which compares favorably with a similar plant piped with alloy steel piping at a cost of $1.33 million. Life-cycle cost analysis indicates that the cost of PC-lined steel pipe …
Date: December 1, 1981
Creator: Kaeding, Albert O.
System: The UNT Digital Library
Design and qualification testing of a strontium-90 fluoride heat source (open access)

Design and qualification testing of a strontium-90 fluoride heat source

The Strontium Heat Source Development Program began at the Pacific Northwest Laboratory (PNL) in 1972 and is scheduled to be completed by the end of FY-1981. The program is currently funded by the US Department of Energy (DOE) By-Product Utilization Program. The primary objective of the program has been to develop the data and technology required to permit the licensing of power systems for terrestrial applications that utilize /sup 90/SrF/sub 2/-fueled radioisotope heat sources. A secondary objective of the program has been to design and qualification-test a general purpose /sup 90/SrF/sub 2/-fueled heat source. The effort expended in the design and testing of the heat source is described. Detailed information is included on: heat source design, licensing requirements, and qualification test requirements; the qualification test procedures; and the fabrication and testing of capsules of various materials. The results obtained in the qualification tests show that the outer capsule design proposed for the /sup 90/SrF/sub 2/ heat source is capable of meeting current licensing requirements when Hastelloy S is used as the outer capsule material. The data also indicate that an outer capsule of Hastelloy C-4 would probably also meet licensing requirements, although Hastelloy S is the preferred material. Therefore, based …
Date: December 1, 1981
Creator: Fullam, H. T.
System: The UNT Digital Library